Integrated Modelling of Nitrogen Seeded JET Discharges

Zagórski, R.; Telesca, G.; Rapp, J.; Contributors, Jet‐Efda

doi:10.1002/ctpp.200810032

Cited by 28 publications

(37 citation statements)

References 12 publications

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“…The nitrogen seeded high triangularity JET discharges have been modelled with COREDIV [41]. COREDIV is an integrated model solving self-consistently the 1D energy and particle transport of plasma and impurities in the core region and 2D multifluid transport in the SOL [42].…”

Section: Extrapolation To Iter With the Integrated Model Coredivmentioning

confidence: 99%

Integrated scenario with type-III ELMy H-mode edge: extrapolation to ITER

Rapp¹,

Corre²,

Andrew³

et al. 2009

Nucl. Fusion

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One of the most severe problems for fusion reactors is the power load on the plasma facing components. The challenge is to develop operation scenarios, which combine sufficient energy confinement with benign heat loads to the plasma facing components. The radiative type-III ELMy H-mode seems a possible solution for such an integrated ITER scenario. Nitrogen seeded type-III ELMy H-modes for the standard inductive scenario and the high beta stationary hybrid scenario are investigated with respect to their transient and steady-state power fluxes to the divertor, confinement properties, edge operational space, core operational space, plasma purity and MHD behaviour. A large database of highly radiative type-III ELMy H-modes on JET is used for extrapolations to ITER. On this basis the transient heat load should be acceptable for ITER. It was found that the scaling of the confinement time with respect to the ion gyroradius is close to the gyro-Bohm scaling. Scalings with respect to the plasma collisionality suggest that the confinement will be good enough for an ITER scenario at 17 MA with a power amplification factor (Q) of 10 and might be marginally good enough for a Q = 10 scenario at 15 MA. Those extrapolations are supported by simulations with an integrated core/edge model COREDIV. In addition the hybrid scenario with type-III edge localized modes has been proven to have improved edge conditions without any modification of the central plasma current profile, indicating it is compatible with a high beta operation for a steady-state ITER Q = 5 scenario.

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Section: Extrapolation To Iter With the Integrated Model Coredivmentioning

confidence: 99%

Integrated scenario with type-III ELMy H-mode edge: extrapolation to ITER

Rapp¹,

Corre²,

Andrew³

et al. 2009

Nucl. Fusion

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“…In view of possible realistic prediction for ITER plasma scenarios, it is necessary to developed validated numerical tools. For this aim, COREDIV code [2] has been constructed, which self-consistently couples the plasma core with the plasma edge and the main plasma with impurities. The code was in the past succesfully benchmarked against a number of JET discharges with carbon plates and impurity seeding [2][3][4] proving its capability of reproducing the main features of JET seeded discharges as the elecrton density and temperature profiles, the total radiated power, and the effective ion charge, Z ef f .…”

Section: Introduction and Physical Modelmentioning

confidence: 99%

Integrated Modelling of Nitrogen Seeded JET ILW Discharges for H‐mode and Hybrid Scenarios

Ivanova‐Stanik¹,

Zagórski²,

Telesca³

et al. 2014

Contrib. Plasma Phys.

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In this paper numerical simulations with COREDIV code of JET discharges with ITER-like wall are presented. We concentrate on the JET H-mode and hybrid scenarios with nitrogen seeding and all simulations have been performed with the same transport model and only the discharge input parameters like auxiliary heating P aux, line average plasma density n is an input parameter in our model and has been kept equal to 0.4 ÷ 0.5n lin e in the simulations, with the recycling coefficient adjusted accordingly. It has been shown that COREDIV is able to reproduce basic parameters of nitrogen seeded discharges for both H-mode and hybrid scenarios. We have achieved reasonable agreement with global plasma parameters like radiations levels, Z ef f and tungsten concentrations and the plasma profiles, including density, temperature and radiation are in very good agreement with experimental data. The agreement of the code results with the experimental data might be even better, if the simulations are further tuned taking into account uncertainties to the sputtering model, separatrix density or SOL transport. Simulations show that the observed Z ef f level is defined mostly by the low Z impurity content, Be and N2 in the considered shots. It has been found that the tungsten radiation plays always very important role and can not be mitigated even by strong influx of nitrogen.

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“…The code has been successfully benchmarked with the nitrogen seeded type III ELMy H-mode discharges on JET [1,2] and with Neon seeded AT scenarios but with Carbon wall [3]. The main discharge parameters, such as temperature and density profiles, total radiated power, Z ef f where nicely reproduced by the code.…”

Section: Introduction and Physical Modelmentioning

confidence: 99%

“…Therefore, to reduce the heat load on the divertor, impurity injection (Ne/N 2 ) is necessary but that might lead to significant tungsten erosion and, as consequence, termination of plasma discharge. This paper describes integrated numerical modeling for the first time applied to AT discharges with tungsten wall using the COREDIV code [1]. Since the energy balance depends strongly on the coupling between the bulk and the scrape-off layer (SOL) plasma, modeling requires the transport problem to be addressed in both regions simultaneously.…”

Section: Introduction and Physical Modelmentioning

confidence: 99%